ML18139B360

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Radiological Progress Rept 4,Mar-Apr 1981.
ML18139B360
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/29/1981
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139B359 List:
References
NUDOCS 8106030168
Download: ML18139B360 (32)
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Text

.J I

STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 1 RADIOLOGICAL PROGRESS REPORT - NO. 4 FOR THE PERIOD MARCH 1, 1981 THROUGH APRIL 30, 1981 DOCKET NO. 50-280 LICENSE NO. DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY

1.B.106 O 30 l(p i

I TABLE OF CONTENTS PAGE NO.

1.0 INTRODUCTION

PR4-1 2.0 OCCUPATIONAL RADIATION EXPOSURES PR4-2 2.1 General PR4-2 2.2 Evaluation of Exposure Data PR4-2 2.3 Description and Format of Exposure Data PR4-3 2.4 Conclusions and Observations PR4-4 3.0 APPLICATION OF ALARA PRINCIPLES PR4-5 3.1 General PR4-5 3.2 Containment Cleanup and Decontamination PR4-S 3.3 Temporary Shielding PR4-S 3.4 Reactor Coolant Piping PR4-7 3.5 Temporary Containments and Ventilation PR4-7 3.6 General Techniques and Practices PR4-8 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE PR4-10 4.1 General PR4-10 4.2 Airborne Releases PR4-10 4.3 Liquid Releases PR4-10 4.4 Solid Radioactive Waste PR4-10 TABLES Table 1 - Personnel Radiation Exposure Summary Table 2 - Report of Radioactive ~ffluents

r

1.0 INTRODUCTION

' PR4-1 SSGP The Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No. 1 commenc_ed on September 14, 1980. This fourth progress report for the Unit No. 1 SGRP contains information on the radiolo-gical effects of the repair effort, and describes the measures taken to maintain these effects "as low as reasonably acheivable" (ALARA), during the period March 1 through April 30, 1981.

With regards to radiological effects, the major tasks completed during the reporting period involved installation activities and post installation and startup activities. By the end of the period all of the major pipe and vessel welding was essentially complete with the exception of one reactor coolant pipe joint. All of the secondary side, and two of the primary side hydrostatic tests were completed.

The . report sections which follow provide an assessment of the occupational exposure expended, the dose reduction techniques employed and their effectiveness, and the radioactive effluents and solid waste generated during the reporting period. Throughout this progress report and those to follow for the Unit No. 1 SGRP, reference will be made wherever appropriate to the progress reports issued during the Surry, Unit No. 2 SGRP for purposes of compari-son, and to identify differences in the replacement activities which have a significant effect on the radiological impact of the program.

I PR4-2 SSGP 2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General Occupational exposure to radiation is considered to be the major radiological effect of the SGRP. As such, this aspect of the pro-ject underwent an extensive evaluation during the planning phase to provide realistic estimates of the amounts of personnel radiation exposure (manrem) which would be required to perform each of the tasks involved. These estimates were based upon the anticipated labor requirements (manhours) and the average radiation dose rates in the work area, and were presented in summary form in Table 5.3-1 of the report entitled "Steam* Generator Repair Program", dated August 17, 1977 and amendments thereto, hereafter referred to as the SGRP Report.

Prior to commencement of the project, a program was established to assess the actual exposures -received by personnel during the repair effort. This program was designed to provide data compatible with the detail and format of the exposure summary presented in Table 5.3-1 of the SGRP Report, thereby permitting valid comparisons between estimated and actual expenditures.

2.2 Evaluation of Exposure Data The exposure ~ssessment program referred to above is basically designed to utilize daily worker exposure data, as recorded by self-reading pocket dosimeters, in conjunction with contractor supplied, worker task data to determine task-related manrem expen-ditures. The worker task data is standardized to a system of discrete work packages (called Engineering Task Assignments) which was developed during the project planning phase. The use of this system to categorize exposure related work for individuals on a daily basis fac~litates the process of compiling an accurate break-down of the collective exposure expended on the many tasks involved.

' ,' 'f I I , PR4-3 SSGP 2.3 Description and Format of Exposure Data Table 1 presents a summary of the occupational radiation exposure expended during the reporting period, the labor and exposure ex-penditures to-date (i.e. from project commencement on September 14, 1980 to April 30, 1981), and the original estimated expenditures.

The following comments are provided for clarification and should be considered when reviewing the data presented.

(a) Additional tasks performed during the repair effort which were not listed in Table 5.3-1 of the SGRP report have been includ-ed in Table 1. Similarily, exposures received by personnel performing functions not directly attributable to any one task have been listed separately.

(b) The "Task Status" indications listed in Table 1 are intended to aid in the process of comparing estimated vs. actual manrem expenditures during the repair effort. For tasks indicated as "in progress", significant exposure related work may remain to be performed and a realistic comparison may be impractical.

For "completed" tasks, the manrem and manhour values listed in Table 1 can be considered to represent the major significant expenditures for those tasks, therefore valid comparisons are possible. It should be recognized, however, that factors such as field changes to procedures, dismantling of task related support equipment, localized work area cleanup, etc. may con-tinue to contribute small amounts of additional exposure and labor to a task for some time after completion is indicated.

(c) The Phase Subtotals listed in Table 1 are calculated by a summation of values for completed tasks. Expenditures report-ed for "Additional Tasks" and "Unassigned Personnel Cate-gories" are allocated to a particular phase based upon the major activities being performed at the time they are incurred. Thus, the Phase Subtotals also include these values for phases in which a majority of the tasks have been complet-ed. This is the case for Phases I and II (Shutdown and Preparatory Activities

  • and Removal Activities). For Phases III and IV, The Phase Subtotals do not yet include the e~pen-ditures mentioned above since a majority of the tasks have yet to be completed.

PAGE 1 of 14 TABLE l PERSONNEL RADIATION EXPOSURE

SUMMARY

STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 3/1/81 - 4/30/81 SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE PHASE ESTIMATED EXPENDED ESTIMATED roR REPORTING EXPENDED STATUS PHASE LABOR TO-DATE EXPOSURE PERIOD TO-DATE ( CmCOMPLETE)

DESCRIPTION ~MANHOURS) (MANHOURS) (MAN-REM) (MAN-~EM) (MAN-REM) {I=IN PROGRESS)

      • COMPLETED TASKS ONLY***

I Shutdown and Preparatory 35,421 46,918 326.27 0.060 147.689 C Activities II Removal Activities 57,422 167,151 559.6 1.026 451.655 C III Installation Activities 14,427 37,155 72.14 8.010 28.864 I IV Post Installation and 13,714 17,841 122.21 5.490 40.808 I Startup Activities V Steam Generator Storage 300 937 35 0 8.079 C Activities PROJECT TOTALS 121,284 270,002 1,115.22 14.586 677.095 (Completed Tasks Only)

  • ~

PAGE 2 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 3/1/81 - 4/30/81 SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE PHASE ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS PHASE LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS)

      • ALL TASKS COMMENCED AS OF 4-30-81***

I Shutdown and Preparatory 39,021 48,962 596.27 4.018 211.879 C Activities II Removal Activities 57,422 167,151 559.6 1.026 451.655 C III Installation Activities 74,195 340,338 448.23 386.167 699.357 I IV Post Installation and 62,650 69,077 427.54 36.091 116.928 I Startup Activities V Steam Generator Storage 300 937 35 0 8.079 C Activities PROJECT TOTALS 233,588 626,465 2,066.64 427.302 1,487.898 (All Tasks)

"t PAGE 3 of 14 TABLE l PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I - SIDJTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. l ACTIJAL LABOR ACTUAL EXPOSURE. ACTIJAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR.REPORTING -EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) {!*IN PROGRESS)

Erect Equipment Hatch 264 0 0.4 0 0 C Temporary Enclosure Prepare and Load Test 210 463 1.05 0 1.285 C Polar Crane Open Equipment Hatch 156 0.23 C (See Note l)

Defueling and Fuel Storage 585 2,863 11. 7 0 23.503 C Install Reactor Vessel 130 695 1.3 0 l.813 C Cavity Cover Cutting of Pressurizer (See Note 2)

  • Cubicle Wall Installation of Jib 'Cranes l ,&38 3,348 9.19 0 5.256 C Disassemble Manipulator. Crane 58 629 l. 74 0 l.533 C Install Steam Generator 572 3,948 2.86 0.003 6.953 C Transport System Removal of Biological 1,296 916 19.44 0 2.298 C Shield Wall

PAGE 4 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I - SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 1 TASK DESCRIPTION Disassemble Shroud Cooling System ESTIMATED LABOR (MANHOURS) 150 ACTIJAL LABOR EXPENDED TO-DATE (MANHOURS) 601 ESTIMATED EXPOSURE (MAN-REM) 3 ACTIJAL EXPOSURE FOR REPORTING PERIOD (MAN-REM) 0 ACTIJAL EXPOSURE EXPENDED TO-DATE (MAN-REM) 1.228 TASK STATUS (C*COMPLETE)

(I*IN PROGRESS)

C Cutting of Crane Wall at 432 586 2.16 0.052 1.208 C Hatch Opening Installation of Temporary 50 106 0.05 0 0.053 C Ventilation System Temporary Scaffolding 7,500 4,846 75 0 14.786 C Temporary Lighting 5,200 2,174 26.25 0 2.162 C and Power Cleanup and Decon 9,000 14,920 135 0 57.975 C Polar Crane Operator 1,500 198 4.5 0 0.137 C Shielding H.P., Q.A.

ADDITIONAL TASKS 3,600 6,480 2,044 6,884 270 32.4 3.958 0

64.190 9.956 I

C '

Installation of Service 627 0 2.198 C Air System

PAGE 5 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I - SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (l*IN PROGRESS)

Work Platform Modification 1,826 0.005 0.746 C Protection of* Containment 1,288 0 6.128 N/A Components UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 0 8.471 N/A and Administration Subtotal Phase I 35,421 326.27 0.060 147.689 (Completed Tasks Only)

PAGE 6 of 14 TABLE l PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. l ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE ( C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS)

Removal of Insulation 720 1,647 28.8 0 14.000 C (lower shell, RC piping)

Removal of Insulation (upper shell, 864 959 12.96 0 5.354 C mainsteam and feedwater piping)

Removal of Miscellaneous 72 1,288 1.8 0 13.896 C Piping Set Up Steam Generator 1,152 90 28.8 0 0.208 C Girth Cut Equipment cut and Remove Steam 330 5,529 8.25 0 9.173 C Generator Upper Shell Cutting of Reactor 2,982 7,181 149.1 0 76.682 C Coolant Piping Cutting of Mainsteam and 1,428 1,399 7.14 0 2.391 C Feedwater Piping Disassembly of Steam 792 6,988 15.84 0 55.120 C Generator Supports Removal of Moisture 396 5,333 1.98 0 9.402 C Separation Equipment Refurbish Steam Generator 9,246 12,874 46.23 0.894 10.781 C Upper Shell

PAGE 7 of 14 TABLE l PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. l ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) ~I*IN PROGRESS)

Removal of Steam Generator Level 135 1,472 4.05 0 6.389 C Instruments and Blowdown Piping Removal of Steam Generator 1,5"?5 4,341 31.5 0.132 22.870 C Lower Shell Temporary Scaffolding 7,500 13,611 75 0 40.919 C Temporary Lighting 5,250 5,356 26.25 0 4.451 C and Power Cleanup and Decon 17,000 44,732 85 0 88.604 C Polar Crane Operator 1,500 2,365 4.5 0 2.428 C H.P., "Q.A. 6,480 27,502 32.4 0 33.740 C I

ADDITIONAL TASKS Material Handling, Equipment  ;..

24,484 0 35.868 N/A Maintenance, and Miscellaneous Construction Activities

PAGE 8 of 14 TABLE 1 .

PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS)

UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 0 19.379 N/A and Administration Subtotal Phase II 57,422

  • 167,151 559.6 1.026 451.655 (Completed Tasks Only)

t PAGE 9 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE III - INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) ~I-IN PROGRESS) ..

Steam Generator Lower 1,926 10,536 9.63 2.863 19.748 I Shell Installation Installation of Reactor 6,768 29,653 67.68 134.643 205.295 I Coolant Piping Steam Generator 5,400 15,553 27 2.984 12.143 C Girth Weld Installation of 3,735 7,036 18.68 0.979 3.335 C Hain Steam Piping Installation of 2,700 6,418 13.5 1.478 2.997 C Feedwater Piping Installation of Blowdown and 1,782 12,118 17.82 36.097 51. 738 I Miscellaneous Piping Install Steam Generator 2,592 8,148 12.96 2.569 10.389 C Level Instruments Installation of 11,562 201 57.81 0.253 0.546 I Insulation Temporary Scaffolding 7,500 21,163 . 75 37.723 67.507 I Temporary Lighting 5,250 6,911 26.25 2.210 4.219 I

& Power

PAGE 10 o_f 14 TABLE l PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE III - INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. l ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDfJ) STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE ( C*COHPLETE)

DESCRIPTION (HANHOURS) (HANHOURS) (MAN-REH) (MAN-REH) (MAN-REH) (I*IN PROGRESS)

Cleanup and Decon 17,000 100,305 85 79.509 158.792 I Polar Crane Operator 1,500 7,292 4.5 0.987 2.861 I H.P., Q.A. 6,480 61,605 32.4 44.851 76.730 I ADDITIONAL TASKS Material Handling, Equip- 53,399 26.649 57.3~ N/A ment Maintenance, and Miscellaneous Construction Activities UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 12.372 25.700 N/A and Administration Subtotal Phase III 14,427 37,155 72.14 8.010 28.864 (Completed Tasks Only)

PAGE 11 of 14 .

TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO, 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS

~

TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) ~I*IN PROGRESS)

Install Biological 3,240 2,742 16.2 3.893 4.811 C Shield Wall Repair Crane Wall 473 91 2.37 0 0.079 C Opening Repair Pressurizer Cubicle (See Note 2)

Wall Install Steam Generator 9,000 12,351 90 1.450 32.849 C Recirculation and Transfer System Remove Reactor Cavity 130 86 0,65 0.170 0.170 I Cover Install Reactor Cavity 240 59 1.2 0.065 0.065 I Coaming Reassemble Manipulator 1,176 1,495 23,25 1.320 1.666 I Crane Remove Steam Generator

  • Transport System Reassemble Shroud Cooling System Hydrostatic Tests 425 576 75 47 2,610 2,428 2.12 11.52 0.38 0

0.147 3.347 0.014 3.055 3.407 C

C I

PAGE 12 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) {MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS)

Refueling 585 0 11.7 0 0 I  :

Temporary Scaffolding 7,500 4,038 75 4.192 11.914 I Temporary Lighting 5,250 1,155 26.25 0.246 0.738 I and Power Cleanup and Decon 17,000 18,045 85 8.834 25.409 I Polar Crane Operator 1,500 1,362 4.5 0.110 0.418 I Painting 9,000 932 45 2.998 4.816 I H.P., Q.A. 6,480 11,597 32.4 4.983 12.972 I ADDITIONAL TASKS I Material Handling, Equipment 10,039 2.961 9.673 N/A Maintenance, and Miscellaneous Construction Activities

PAGE 13 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE :

TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS*

TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE ( C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) . (MAN-REM) (MAN-REM) (I*IN PROGRESS)

UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 1.375 4.872 N/A and Administration Subtotal Phase IV 13,714 17,841 122.21 5.490 40.808 (Completed Tasks Only)

-e

PAGE 14 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE V - STEAM GENERATOR STORAGE ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE ( C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (kAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS)

Steam Generator Storage 300 937 35 0 8.079 C Activities TABLE NOTATION

1. Labor and Exposure expenditures for this task were included in other task totals. (Primarily "Defueling and Fuel Storage").

Labor and Exposure estimates are included in the Subtotal Values.

2. "nlis task was cancelled due to equipment changes. Labor and Exposure Estimates are not included in the Subtotal Values.

N/A - Not Applicable. Labor and Exposure Expenditures are included in the Subtotal Values for Phases I and II. They are not included in the Subtotal Values for Phases III and IV (See Report Section 2.3.c).

e e

TABLE 2 SURRY POWER STATION PAGE 1 of *6 STEAM GENERATOR REPLACEMENT PROJECT i REPORT Of RADIOACTIVE EFFLUENTS YEAR: 1980

  • t

- ~ - --. - *---- -- - . -

September October Novemher - . - *-- -~:r-.*

UN1:TS I. LIQUID RELEASES. Curies Isotooe: Released MPC UCi/ml 3 X 10-'l I-131 S.96E-5 4 O'l1" .. Cj

? '"'"'-1

  • I-132 8 X 10-6 I-133 1 X 10-6
1. 73E 6 1.32E-5 3.47E-7 I-134 2 X 10- 0 4 X 10-*

I-135 * * *

  • Cs-134 9 X 10-* 3.0lE-4 8.32E-4 2.48E-2 Z.:Jo~-4 Cs-137 2 X 10- 0 1.04E-3 2.38E-3 3 35E-2 8.0BE-4 Co-:'I/ 4 X 10-*
  • l.89E-6 3.57E-7 -- *-

Co.-:>ll g X 10-" S.73E-4 1 '""'-1 l.36E-2 ~.oOE-4 Co-bU 3 X 10- 0 1.lOE-3 'i 72F.-3 l.81E-2 3 .48E-3 Mn-54 1 X 10-" 3.36E-5 1 llE 4 2.78E-3 4.45E-5 Na-24 3 X 10-*

  • l.17E 3 6.29E-3 '*--

Cr-51 2 X 10-* 1.14E~4 1.99E-4 4.87E-4

  • Fe-59 Nb-95 5 X 10-5 1 ... , n_ *
1. llE-5 * * **

5.68E-5 3.66E-5 1 2'l1" .,;

Sb-124 '} V 10-"

  • 1.20E-6 -*

Sb-12:'I 1 ,r 10- 4

  • 3.86E-5 7 .SOE-7 1.44E-6 Zn-b:'I 1 X 10- 4 2.60E-6 Zr-9:'I * *
  • 6 V 10- 0 *i1r * *
  • Ru-103 8 X 10- 0
  • l.89E-6 * * ..

Xe-133 3 X 10-* 8.66E-5 4.74E-4 1.BSE-2 3.68E-6 Xe-135 3 X 10-*

  • 7.48E-5 2.41E-3
  • Xe-133m 3 X 10- 6
  • 1.lSE-5 *
  • Ag-llUm N1-t,J 3 X 10-'

l.OOE-3 3 X 10-5 4 OlE-5 1.41E-3 l.J.SF.-3 8 X 10- 0 Fe-55 1.16E-4 l.12E-2 **

Ce-144 1 X 10-*

  • 1.77E-7 Tc-99m 3 X lU-'

':IX lU- 0 Ce-141

  • 9.0BE-7 * "

Volume of Liquid to Discharge Canal IT.~'"--- 6.70E+4 S.89E+S 1.16E+6 4.76E+S

  • Not Det.ected
    • Sample analysis results not yet received from service vendor.

Upon receipt, analysis data will be included in subsequent proe;ress rl'!1>orte,

TABLE 2 SURRY POWER STATION PAGE 2 of_6__

STEAM GENr:RJ\TOR REPT ,ACl-1-ffiNT PROJECT REPORT OF RADIOACTIVE EFFWENTS YEAR: 1980

*- - --**- - . ~..-~~- -- - - *- --

I II, r~ - -- - - - - - - -~.,.,_ - -- *'---~- -- - - --- - ii NIRBORNE RELEASES ' UNITS September October November  ! December

==- - - *-. .... ...-'"T ,_ -- :,;~---

-- -**- -~ ~~~ - - *---* *- **----- *-

I i

--Ii

,~*Isotopes Reieased: Curies (a) Particulates Cs-134 - 3.12E-6 1 221".-6 2.73E-6 Cs-137 9.07E-6 1. 76E-5 8,66E-5

  • e Cr-51 4.42E-5 1.65E-5
  • Co-58 2.63E-5 5,02E-5 l.65E-5 l.94E-5 Co-60 3.49E-5 c;_ ac;ta>_i; S.97E-5 6.27E-5 Mn.:.54 * *
  • Fe-59
  • Cs-138
  • 1.0lE-4 Rb-88 c; ?/,ta' .. c;

,b) Halogens I-])l 1. 78E-3 (:. 151<' .b. 7 .90E-7i 1.74E-5 '

I-132 4.73E-6 2.12E-6

  • 4.03E-5 1.31E-6 I-133 2-31E-5 I-1':\b. * * * * ,.

T-1 "1'-

  • * * * 'I (c) Gases 4,44E+2 S.26E+l
  • Xe-133 S.22EO Xe-133m 7.89EO Xe-135 Kr-85m 3.21E-1 Kr-85 * * *-'Ir
  • Kr-87 * *
  • Kr-88 * * *
  • Ar-41 * * * "

Xe-131m 5.4SE+2 * "

H-3 7 .08E-1 2,lSE-1* 6.97E-2 5,62E-2 -.

  • 7t ii-

~ -

,I

[=-: -. "

  • Not Detected
      • --*------- *-* -------.~~-- . ----~~-~---- ---*-- ~ - -* -- -

- - - - - - ~ - - - - - - - - - -- ----

TABLF. 2 SURRY PO\.TER STATION PAGE 3 of STEAM GENERATOR REPLACEMENT PROJECT -

REPORT OF RADIOACTIVE EFFLUENT~

YEAR: 1980 III. SOLID RADIOATIVE WASTE DISPOSAL ~-- --* -

/ Units

- SPnt..e,.'!'b!'_r- ()('+-~l,.,.,.

-- _..lloyfml-.or n.,~.,".'b..e.r_ ~-*:-**--

Isotopes Released: Cur:Les (a) Total Amount of Solid Haste Packaged I FT3 0 3.94E+3

  • 6.30E+3 l.64E+4 (b) Estimated Total Activity Curies o. 1 4SE+o 1.82E+l 8.54E+O (c) Date of Shipment and !11 to

~:gwell,

!11 to arnwell, !klrnwell to Disuosition - .0 "' ~ r s r 10-15-80 11-3-Afl 12-1-80 (2) '.

- - 10-21-80 11-4-80 12-2-80 (2) 10-23-80 11-6-80 12-3-80 (2)

.. 10-28-80 11-7-80 (2) 12-4-8Q (2)

- 10-30-80 11-10-RO 11-12-80 12-5-80 (2) 12.-8-80

' ._ 11-13-80 12-11-'80(2)

.. 11-14-80 12.-I2-80

-- 11-18-80(2) 12-15-'80

-- 11-19-80 12-16-8.0 12-I7-80 12-18-80 12-19-80 -

12-22-80, 12-30-80(2) e

>'<Not Detected

TABLE 2 J.

.. SURRY POWER.STATION PAGE 4 of 6

. -REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1981

. JANUARY FEBRUA.~Y MARCH APRIL '

UN1:TS I. LIQUID RELEASES Curies lsotooe: Released HPC UCi/ml 1-131 J X 10-1 l.32E-6 * *

  • 8 X 10- 6 .,..

1-132 1 X 10- 6

  • * ~

1-133 * * *

  • 1-134 2 X 10-b * ,.

4 ][ 10- 11 I 135 Cs-134 9 X lO-"

  • 6.00E-4 fr 2.lOE-4 4.0lE-4 9.41E 4 Cs-137 2 X lo-* l.49E-3 l.60E-3 9.02E-4 1.83E-3 Co-57 4 X lo-~ 8,28E-7 l.27E-5 l.52E-7 9,09E-7 Co;-58 !r X lo-* l,69E-3 6.SOE-4 2,28E-4 l.94E-3 Co-60 J X lo-* 7,64E-3 4,30E-3  ? ,. ~" -~ 7.0BE-3 Mn-54 .1 X lo-~ 1.81E-4 . 5.00E-5 -, '>RJ;"_,; 9.02E-5 Na-24 J X lo-* 2.00E-4 Cr-51 2 X 10-*
  • 2.21E-5 *
  • Fe-59 i; .. 1n_ 9 Nb-95 Sb-124 1 .. ,n_ ~

2,. 1n_b 3.07E-5 4,80E-6

. S.86E 6 Sb-125 1.., ln-" ~.13E-6* 2.30E-4 ~ ,,.,,,_,; 1.03E- 4 Zn-65 1.., in-"

  • 1.25E-6 Zr-95 6 ,r 10-b :It fr *
  • Mo-99 & ,. ln- 5 ... ... *
  • Ru-103 Xe-133 8 X 10- 5 ...

o,,.._.,

3 X 10-" i; 1 nm,_'>.

Xe-135 J X 10-" fr Xe-133m J X 10- 6

  • 1 nm,_1..
  • 1 nn,,_,;

Ar-41 * *

  • J X 10- 5 *
  • Nt-llUm J X 10-* * .. .,.*

J X 10- 5 * *

  • Ni-bj 1.onE-6.

4 lOE-7 **..,. **

Fe-55 Ce-144 Tc-99m 8 :K 10-D

. 1 X lU- 5 3 X 10-*

1.31E 5

  • fr e

Ce-141 9 X .1u-*

Volume of Liauid to Discharge Canal T~loa*- 7.40E+5 l3.00E+5 9.02E+S .8 ,45E+S

  • Not Det~ted
    • Sample analyaia results not yet received from service vendor, Upon receipt, analysia data will be included in subsequent progress reports.

TABLE 2 SURRY POWER STATION PAGE. 5* of 6 STEAM GENERATOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1981

- I JANUARY FEBRUARY MARCH APRIL II. AIRBORNE RELEASES

~UNITS 'I Isotones Released: Curies (a) Particulates Cs-134 l.69E-5 Cs-137 1.15E-4 7.13E-6 1*ni;F_/;

. 1 .V'iF-'i

,; no,,._,:;

? 'lOR;...'i Cr-51 Co-58

  • 2.82E-4 Co-60 . 5.44E-4 1.24E-4
  • 1 /;liF-'i

?

,;o~ "

-,:;o,,. _,,

Mn-54 Fe-39' l.92E-5 Cs-138 * * *

  • Rb-88 Nb-95 (b) Halogens *
  • 1 -:i,:;,,._i; I-'Til 2.15E-:-6 I-132 1-133 * * *
  • 1-134 * * * *

. *I-135 (c) Gases Xe-133 Xe-133m I

Xe-135 Kr-85m Kr-85 Kr-87 * * *

  • Kr-88 * * *
  • Ar-41

. 5.BOE-2 .J,33E-2 3 .97E-2 7 ?n1" I

  • Not Detected

TABLE 2 SURRY.POWER STATION PAGE. 6

~- of - 6 STEAM GENERATOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENTS YEAR:_1981 JANUARY FEBRUARY MARCH APRIL III, SOLID RADIOACTIVE WASTE DISPOSAL ..

Unite Isotopes Released: Curies

{a) Total Amount of Solid Waste '------ I t I I 3

Packaged FT 7.48E+3 l.01E+4 l.07E+4 4.27E+3 ..

(b) Estimated Total Activitv Curies 6,32E+o 9 .34E-l 2.21E+O l.12E+o (c) Date of Shipment and Barnwell, Barnwell, Bal!nwell, Barnwell, Disi>oeition s.c. s.c. .s.c. s.c .

1 .t;-Rl  ?-"1-Rl 3-2-81 4 2-81 1-R-Rl  ?-l,_R1 3-3 81 4-4-81 1-Q-Rl ?_r;._R1 3 6-81 4-9-81 1_1':I-R1 ,_t:_a, 3-10-81 4-21-81 1 .16.-Rl  ?-1n-R1 3-11-81 4 24 81 1-1 r;._Rl  ?-1 ?-R1 3_,t: 81 4 28-81 1 _?n-R1 '>-1'l_R1 ':I -17 .R1 1-?1-A1 'J _1t:_R1 1-1Q-R1 1-?t;-Rl  ?-1R-R1 1-'"'-R1

,_.,n. .R1 'l_.,.,_.,,

'>_'>n_a, 'l ""-R1 e

-* PR4-4 SSGP 2.4 Conclusions and Observations As of the end of the reporting period, the SGRP for Unit No. 1 has been in progress for approximately thirty two weeks. It is apparent at this point in the outage that less exposure is being accumulated in comparison to the Unit 2 outage. This is attributable to a number of factors. Many of the workers and supervisors are the same ones that performed the work on Unit 2 so they are familiar with the work. In addition, steps were taken in preparation for the Unit 1 outage to eliminate problems encountered in Unit 2 and to stream line the procedures. A comparison of the exposure attri-butable to reaching the same milestone events in Unit 2 that have now been reached in Unit 1 shows that Unit 2 took about 1850 man-rem to reach approximately the same point that Unit 1 took 1488 to reach, or a savings of about 362 man-rem. It also should be noted that these milestones were reached in Unit 1 about 60 days earlier than in Unit 2.

3.0 APPLICATION OF ALARA PRINCIPLES

    • PR4-5 SSGP 3.1 General This section summarizes the specific techniques and practices which were employed during this reporting period in order to maintain occupational exposures to radiation "as low as reasonably achiev-able" (ALARA). Where the available data permits, the following evaluations include a quantitative assessment of the manrem savings which can be attributed to the technique used. Additional i~for-mation on these techniques and how they relate to the overall steam generator replacement activities can be found in the SGRP Report.

3.2 Containment Cleanup and Decontamination After shutdown and the removal of all fuel from the reactor, a general cleaning of the containment interior was performed to remove loose radioactive contamination in the work areas and there-by reduce the potential for airborne contamination during subsequent activities. Where appropriate, removable floor covering (plastic sheeting) has been applied to facilitate additional cleanup during the repair activities. A special work crew has been retained to continuously clean the work areas and to perform equipment deconta-mination. This effort will maintain optimum radiological working conditions and avoid buildups of debris.

While it is not possible to quantify the exposure savings attri-butable to this technique, the benefit of maintaining effective control of contamination is seen in terms of its contribution to minimizing the overall hazard associated with the SGRP.

3.3 Temporary Shielding The use of temporary shielding resulted in significant reductions in personnel radiation exposure during the SGRP for Unit No. 2. A separate work package was devoted to the design and installation of this shielding, with particular emphasis placed on the lower steam generator cubicles where radiation levels are highest and several major removal and installation activities are performed. While the temporary shielding applied to these areas in Unit No. 2 was sue-

.I ,.e

\

,.

  • PR4-6 SSGP cessful in minimizing exposure rates for subsequent activities, the task of installing the shielding required a significant amount of exposure (approximately 143 man-rem). In Unit No. 1, the benefit of this previous experience and the use of personnel with
  • specific expertise in the installation of lead shielding has resulted in a considerable reduction in the tim_e and exposure incurred for this task. As seen in Table 1, the shielding performed thus far during the SGRP has tota_led 64 man-rem. Additional shielding may be utilized during the remainder of the project; however, the major portion of this task with respect to its exposure "cost" has been completed. Detailed radiation surveys, performed prior to and after the installation of temp*orary shielding, have been used to assess the effectiveness of this technique in providing net reductions in personnel exposure for two of the major installation activities performed during the reporting period.

(a) The fitup and welding of the reactor coolant piping continued during this reporting period and has now accounted for 205 man-rem. Lead shielding resulted in a dose rate reduction factor of about 6 as described in PR2 which results in a total calculated exposure savings of 1025 man-rem.

(b) The installation of miscellaneous piping and steam generator instrumentation has resulted in the expenditure of approxi-mately 62 man-rem to-date. Lead shielding resulted in a dose rate reduction factor

  • of about* 5 as described in PRl which.

results in a total calculated exposure savings of 248 man-rem.

The assessments described above represent a major portion of the overall benefits expected to result from the application of temporary shielding techniques during this reporting period. All of the removal activities have been completed at this time. There are however, installation activities still to be performed which will benefit from the shielding already in place. Subsequent pro-gress reports will provide further assessments of the "benefits and costs" of this ALARA technique.

PR4-7 SSGP 3.4 Reactor Coolant Piping The largest single expep.diture of personnel exposure during this reporting period was attributable to the welding of the reactor coolant piping (135 of the 427 man-rem expended for the period). As of April 30, 1981 almost all of the reactor coolant pipe welding was complete with the exception of one weld joint which was still to be completed. The total man-rem expended to date on this acti-vity is 205 man-rem which compares favorably with the 308 man-rem expended in Unit No. 2 to reach approximately the same point or a savings of about 103 man-rem. This dose savings is attributable to two factors:

In the Unit No. 2 outage, the old reactor coolant pipe was decontaminated and reused. In Unit No. 1 new reactor coolant pipe elbows were purchased.

In addition, in the Unit No. 2 outage, three (3) sections of reactor coolant piping were removed from each loop versus two (2) in Unit No. 1.

3.5 Temporary Containments and Ventilation To a large degree, the inital containment cleanup and decontamina-tion has minimized the need for extensive use of temporary contain-ments such as tents and glove boxes to control the spread of conta-mination. In areas where significant cutting and grinding work must be performed on highly contaminated piping and components, however, temporary containments have been constructed and are being effectively utilized.

The most significant application of this technique has been made in the lower steam generator cubicles, where the welding of reactor coolant and miscellaneous piping is performed. In Unit No. 1, the lower cubicle for each steam generator has been totally enclosed to transform the entire room into *a single containment. Portable ventilation units continuously draw air from these enclosures through appropriate filters whenever cutting or grinding operations are in progress. Personnel working inside the cubicles are required

PR4-8 SSGP to wear respiratory protection equipment during these operations, and until the ventilation flbw has effectively reduced the air-borne radioactivity to acceptable levels.

Additional tent enclosures have been constructed in various loca-tions to provide controlled work areas for pipe cutting, component refurbishment and equipment decontamination. Portable, filtered ventilation is provided to these enclosures as appropriate.

The benefits observed to-date for these ALARA techniques are three-fold.

(a) The use of small glove boxes for individual pipe cuts has been eliminated. These devices require considerable time and exposure to install and remove, and during the Unit 2 SGRP were found in many cases to be counter-productive to ALARA due to this fact.

(b) The use of temporary containments, especially as applied to the lower steam generator cubicles, has largely eliminated delays and interference with work being performed in adjacent areas while cutting and grinding of contaminated piping is in progress.

(c) The overall potential for airborne contamination and problems associated with contamination control have been minimized by effective use of temporary containments and portable ventila-tion.

3.6 General Techniques and Practices In addition to the specific dose reduction techniques described thus far, it is important to note the more general procedures and practices which have been implemented to assure adequate control of occupational radiation exposure and to maintain this exposure ALARA. These include:

(a) A comprehensive health physics program to provide adequate control and surveillance of the radiation hazards associated with each task. This program includes the use* of Radiation Work Permits (RWP' s) with an individual "sign-in" system to ensure worker familiarization with the specific radiological

PR4-9 SSGP hazards involved and proper protective measures to be taken in the performance of their work.

(b) A training program to provide adequate instruction in the biological effects of radiation exposure, radiation protection practices and applicable federal regulations, to all personnel involved in steam generator replacement activities. Training for specific tasks, using mock-ups, photographs, or "dry runs" is conducted where appropriate. Additionally, the video-tape documentation compiled during the Unit No. 2 SGRP is being utilized to provide all personnel with a general understanding of the repair program. In this way, each worker is more fami-liar with the sequence of events to take place and the manner in which individual tasks relate to the overall repair effort.

(c) The use of discrete "Work Packages" to assure adequate pre-planning and review of specific tasks, with special emphasis placed on minimizing the radiation exposure to personnel involved.

(d) The establishment of "rest areas" to accommodate workers during idle periods. Rest areas within the containment are located where exposure rates are low (2-3 mR/hour on the average). Additionally, for the Unit 1 replacement a "rest trailer" has been located outside the containment equipment hatch on the operating deck level where radiation levels are typically 0.1 mR/hour. These rest areas are well posted for identification and workers are encouraged to utilize these areas whenever possible to avoid unnecessary exposure.

Although quantitative assessments are not possible for these "general" techniques, all have obvious value in contributing to the overall ALARA program for the steam generator replacement project.

PR4-10 SSGP 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 4.1 General Radioactive liquid and gaseous effluents, and radioactively conta-.

minated solid wastes generated during the SGRP for Unit No: 1 are attributable to several sources. In general, these sources can be distinguished with reasonably accuracy from those associated with concurrent operation of Unit No. 2, even though shared processing systems are utilized in some cases.

4.2 Airborne Releases Airborne releases during the reporting period originated primarily from the continuous ventilation of the containment during the repair effort, to maintain a negative pressure while the equipment hatch is open. This continuous ventilation is processed through appropriate filter banks to minimize the concentration of airborne particulates which may result from activities inside the contain-ment.

4.3 Liquid Releases The major contributor to liquid releases during this reporting period continues to be disposal of laundry waste water. Laundry wastes are expected to comprise the predominant .source of liquid releases during the remainder of the repair effort, as was observed during the SGRP for Unit No. 2.

4.4 Solid Radioactive Waste The disposal of contaminated paper waste, disposable protective clothing and contamination control materials, and, to a lesser degree, structural materials and components not intended for reuse continued to comprise the major portion of the solid radioactive waste generated during the reporting period.

The quantities of radioactive materials released in liquid and gaseous effluents, and the amounts of solid radioactive waste shipped offsite for disposal during this reporting period are summarized in Table 2.

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